Uncertainty analysis of minimum vessel liquid inventory during a small-break LOCA in a B W Plant: An application of the CSAU methodology using the RELAP5/MOD3 computer code
| Autor: | L S Ghan, M G Ortiz |
|---|---|
| Rok vydání: | 1992 |
| Předmět: |
Engineering
Source code business.industry media_common.quotation_subject Pressurized water reactor Process (computing) Reliability engineering law.invention Operator (computer programming) Robustness (computer science) law Code (cryptography) Transient (computer programming) business Uncertainty analysis Simulation media_common |
| DOI: | 10.2172/6771672 |
| Popis: | The Nuclear Regulatory Commission (NRC) revised the emergency core cooling system licensing rule to allow the use of best estimate computer codes, provided the uncertainty of the calculations are quantified and used in the licensing and regulation process. The NRC developed a generic methodology called Code Scaling, Applicability, and Uncertainty (CSAU) to evaluate best estimate code uncertainties. The objective of this work was to adapt and demonstrate the CSAU methodology for a small-break loss-of-coolant accident (SBLOCA) in a Pressurized Water Reactor of Babcock Wilcox Company lowered loop design using RELAP5/MOD3 as the simulation tool. The CSAU methodology was successfully demonstrated for the new set of variants defined in this project (scenario, plant design, code). However, the robustness of the reactor design to this SBLOCA scenario limits the applicability of the specific results to other plants or scenarios. Several aspects of the code were not exercised because the conditions of the transient never reached enough severity. The plant operator proved to be a determining factor in the course of the transient scenario, and steps were taken to include the operator in the model, simulation, and analyses. |
| Databáze: | OpenAIRE |
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